Abstract
Six Joint European Torus (JET) divertor tiles were coated with tungsten marker stripes for erosion/deposition studies. The average thickness was 3.4 μm and the film was uniform within 5% across and within 10% along the stripe. Small amounts of impurities C, Fe, Ni and Cr were found and the in-plane stress was 965 MPa. Resistance to high heat loads was tested in the Neutral Beam Test-bed at JET where a coated carbon fibre composite block was exposed to a total of 113 pulses with a maximum peak power density of 15.7 MW m−2 and a maximum surface temperature of 1280 °C. No visible changes as a result of thermal cycling nor sputtering of the film by deuterium could be detected.
Original language | English |
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Pages (from-to) | 241-245 |
Number of pages | 5 |
Journal | Fusion Engineering and Design |
Volume | 66-68 |
DOIs | |
Publication status | Published - 2003 |
MoE publication type | A1 Journal article-refereed |
Event | 22nd Symposium on Fusion Technology - Helsinki, Finland Duration: 9 Sept 2002 → 13 Sept 2002 Conference number: 22 |
Keywords
- tungsten coating
- plasma
- tungsten
- erosion
- deposition
- divertor tiles
- divertor
- JET
- ITER
- fusion energy
- fusion reactors